Effect of dynamic strain aging on the leak-before-break analysis in SA106 Gr.C piping steel
Creators
- 1. Korea Adv. Inst. of Sci. and Technol., Seoul (Korea, Republic of). Dept. of Nucl. Eng.
Description
The characteristics of dynamic strain aging (DSA) on material properties used in leak-before-break (LBB) analysis were discussed. Using these material data, the effect of DSA on the LBB analysis was estimated through the evaluation of leakage-size crack and flaw stability in SA106 Gr.C piping steel. Also, the results were represented as a form of 'LBB allowable load window'. In the DSA temperature region, the leakage-size crack length was smaller than that at other temperatures and it increased with increasing tensile strain rate. In the results of flaw stability analysis, the lowest instability load appeared at the temperature corresponding to the minimum J-R curve which was caused by DSA. The instability load depended on the loading rate of J-R data, and decreased with increasing tensile strain rate at the plant operating temperature. These are due to the strain hardening characteristic and strain rate sensitivity of DSA. In the 'LBB allowable load window', the LBB allowable region at the temperature and loading conditions where DSA occurs was decreased by about 30% compared with that in other conditions. (orig.)
Additional details
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 174
- Journal Issue
- 1
- Journal Page Range
- p. 59-67.
- ISSN
- 0029-5493
- CODEN
- NEDEAU
Conference
- Title
- Japan-Korea workshop in the integrity of nuclear components.
- Dates
- 8 May 1996.
- Place
- Daejon (Korea, Republic of).
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Switzerland
- INIS RN
- 29011469
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CRACK PROPAGATION; FRACTURE MECHANICS; FRACTURE PROPERTIES; FRACTURES; LEAK TESTING; PIPES; REACTOR MATERIALS; STEEL-ASTM-A106; STRAIN AGING; STRAIN HARDENING; STRAIN RATE; TEMPERATURE RANGE 0273-0400 K; TEMPERATURE RANGE 0400-1000 K; YIELD STRENGTH
- Descriptors DEC
- AGING; ALLOYS; CARBON ADDITIONS; CARBON STEELS; FAILURES; HARDENING; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; MECHANICAL PROPERTIES; MECHANICS; STEELS; TEMPERATURE RANGE; TESTING; TRANSITION ELEMENT ALLOYS
Optional Information
- Notes
- 19 refs.